NEA-0499 HYDY-B1.
HYDY-B1, Channel Thermohydraulics During LOCA of BWR, PWR
NAME OR DESIGNATION OF PROGRAM, COMPUTER, NATURE OF PHYSICAL PROBLEM SOLVED, METHOD OF SOLUTION, RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM, TYPICAL RUNNING TIME, UNUSUAL FEATURES OF THE PROGRAM, AUXILIARIES, STATUS, REFERENCES, REQUIREMENTS, LANGUAGE, OPERATING SYSTEM, OTHER RESTRICTIONS, NAME AND ESTABLISHMENT OF AUTHOR, MATERIAL, CATEGORIES
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To submit a request, click below on the link of the version you wish to order.
Only liaison officers are authorised to submit online requests. Rules for requesters are
available here.
| Program name | Package id | Status | Status date |
|---|---|---|---|
| HYDY-B1 | NEA-0499/01 | Tested | 01-FEB-1979 |
Machines used:
| Package ID | Orig. computer | Test computer |
|---|---|---|
| NEA-0499/01 | IBM 370 series | IBM 370 series |
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4. METHOD OF SOLUTION
The one-dimensional heat conduction equation for a single rod and the one-dimensional equations of conservation of mass, energy and momentum are cast into difference equations and then are solved by explicit integration. Main inputs to the code are the temporal variations of mass flow rate, average specific enthalpy and pressure at the channel inlet.
The one-dimensional heat conduction equation for a single rod and the one-dimensional equations of conservation of mass, energy and momentum are cast into difference equations and then are solved by explicit integration. Main inputs to the code are the temporal variations of mass flow rate, average specific enthalpy and pressure at the channel inlet.
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10. REFERENCES
- "Safety Evaluation Guide Line for Emergency Core Cooling Systems
of Light Water Cooled Nuclear Power Reactors"
Committee on Reactor Safety Examination
Japanese Atomic Energy Commission
May 24, 1974. April 15, 1975 (rev. 1). In Japanese.
- N. Zuber and F.W. Staub:
Nucl. Sci. Eng. 30, 268 (1967).
- R.B. Bird, W. Stewart and E.N. Lightfoot:
"Transport Phenomena"
John Wiley and Sons, Inc., New York (1960).
- K. Shure:
"Fission Product Decay Energy"
Report WAPD-BT-24 , Westinghouse Atomic Power Division, (1961).
- Proposed American Nuclear Society Standard:
"Decay Energy Release Rates Following Shutdown of Uranium-Fueled
Thermal Reactors"
Approved by Subcommittee ANS-5, ANS Standard Committee
(October 1971, Revised October 1973).
- H. Blasius:
Forsch. Arb. Wes., Nr. 131 (1924).
- H.C. Hottel:
"Radiation Heat Transmission"
Chapter 4 of "Heat Transmission" by W.H. McAdams McGraw-Hill
(1954).
- M. Jacob:
"Heat Transfer", vol. 1
New York, Wiley and Sons (1957).
- W.H. Jens and P. Lottes:
"Analysis of Heat Transfer, Burnout, Pressure Drop and Density
Data for High-Pressure Water"
ANL-4627 (1951).
- D.C. Groeneveld:
"An Investigation of Heat Transfer in the Liquid Deficient Regime" AECL-3281 (rev.) (December 1968. Revised August 1969).
- D.M. McEligot, L.W. Ormand and H.C. Perkins, Jr.:
Trans. Amer. Soc. Mech. Engrs., 88, Series C, p. 239-245 (May
1966).
- B.C. Slifer and J.E. Hench:
"Loss-of-Coolant Accident and Emergency Cooling Models for General Electric Boiling Water Reactors"
NEDO-10329 General Electric Company, Equation C-32 (April 1971).
- "Safety Evaluation Guide Line for Emergency Core Cooling Systems
of Light Water Cooled Nuclear Power Reactors"
Committee on Reactor Safety Examination
Japanese Atomic Energy Commission
May 24, 1974. April 15, 1975 (rev. 1). In Japanese.
- N. Zuber and F.W. Staub:
Nucl. Sci. Eng. 30, 268 (1967).
- R.B. Bird, W. Stewart and E.N. Lightfoot:
"Transport Phenomena"
John Wiley and Sons, Inc., New York (1960).
- K. Shure:
"Fission Product Decay Energy"
Report WAPD-BT-24 , Westinghouse Atomic Power Division, (1961).
- Proposed American Nuclear Society Standard:
"Decay Energy Release Rates Following Shutdown of Uranium-Fueled
Thermal Reactors"
Approved by Subcommittee ANS-5, ANS Standard Committee
(October 1971, Revised October 1973).
- H. Blasius:
Forsch. Arb. Wes., Nr. 131 (1924).
- H.C. Hottel:
"Radiation Heat Transmission"
Chapter 4 of "Heat Transmission" by W.H. McAdams McGraw-Hill
(1954).
- M. Jacob:
"Heat Transfer", vol. 1
New York, Wiley and Sons (1957).
- W.H. Jens and P. Lottes:
"Analysis of Heat Transfer, Burnout, Pressure Drop and Density
Data for High-Pressure Water"
ANL-4627 (1951).
- D.C. Groeneveld:
"An Investigation of Heat Transfer in the Liquid Deficient Regime" AECL-3281 (rev.) (December 1968. Revised August 1969).
- D.M. McEligot, L.W. Ormand and H.C. Perkins, Jr.:
Trans. Amer. Soc. Mech. Engrs., 88, Series C, p. 239-245 (May
1966).
- B.C. Slifer and J.E. Hench:
"Loss-of-Coolant Accident and Emergency Cooling Models for General Electric Boiling Water Reactors"
NEDO-10329 General Electric Company, Equation C-32 (April 1971).
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NEA-0499/01
| File name | File description | Records |
|---|---|---|
| NEA0499_01.001 | SOURCE PROGRAM (F4,EBCDIC) | 5728 |
| NEA0499_01.002 | SAMPLE PROBLEM INPUT DATA | 51 |
| NEA0499_01.003 | SAMPLE PROBLEM PRINTED OUTPUT | 1191 |
Keywords: BWR reactors, heat transfer, hydraulics, loss-of-coolant accident, one-dimensional, pwr reactors, reactor channels, reactor safety, thermodynamics.